ML20125A596

Requests Review of Util 710401 Application for Amend to License Re Gaseous Radwaste Sys Mods

ML20125A596
Person / Time
Site:	Monticello
Issue date:	05/11/1971
From:	Boyd R US ATOMIC ENERGY COMMISSION (AEC)
To:	Harold Denton US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212080409
Download: ML20125A596 (2)

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May 11, 1971 Harold Denton, Assistant Director for Site & Radiological Safety Division of Reactor Licensing REVIEW PLAN FOR NORTHERN STATES POWER COMPANY - MONTICELLO NUCLEAR GENERAT-ING PLANT E-5979, TECHNICAL SPECIFICATTON CHANGE REQUEST (GASEOUS RADWASTE SYSTEMMODIFICATION),DOCKETN0(50263) T 4

Northern States Power Company filed a request dated April 1, 1971, to change the Technical Specifications covering proposed modifications to the gaseous radwaste system for the Monticello Nuclear Generating Plant, License No.

DPR-22. Victor Benaroya is the Project Leader.

The proposed system described in a report prepared by NUS, is designed to handle 28 SCFM air inleakage and a holdup time of 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. The modifi-cation to the originally installed offgas system consists of redundant hydrogen recombiners and compressors, and 5 gas storage tanks which will hold gases at 300 psig.

The proposed release lates are the same as in the original Technical Speci-fications and do not reflect the installation of the new equipment. The halogens. calculated doses do not seem to include contributions from licensee's 4

The calculated dose at the nearest boundary for accident conditions is compared to 10 CFR Part 100 guidelines, whereas in PWR's accidents involv-ing storage tanks designed to seismic Class II requirements are considered tolerable if resulting doses are less than 10 CFR Part 20 limits.

The licensee has superficially discussed releases from plant startup, from HPCI turbine and SGTS systens operation and from the steam turbine gland seal system. Radioactive releases from these sources may be appreciable when compared to condenser offgas values after the accepted decay time.

Possible leakage from the compressor or from the pressurized system has not been considered. The report also lacks an analysis of the consequences of malfunctions of equipment and instrumentation. The evaluation of the hypothetical hydrogen explosion has unsupported conclusions.

Technical assistance including a draft report of your evaluation in the following areas is requested.

1. Conformance of the proposed offgas treatment system with the intent of recent changes to 10 CFR Parts 20 and 50 on radiation exposures and releases of radioactive gases to unrestricted areas under normal and abnormal operating conditions.

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2. The appropriateness of the design dose rates with their associated radiation exposure zones and personnel stay-time, considering the limitations of 10 CFR Part 20.

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3. The radiological consequences of the postulated accidents.

4. Hodifications to the Technical Specifications.

4 The review should proceed on-a timely basis in order to enable transmission of any questions you may have to the Project Leader prior to May 31, 1971.

- We expect to publish our evaluation on the proposed design by July 1, 1971.

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Roger S. Boyd, Assistant Director for Boiling Water Reactors 4

Division of Reactor Licensing

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